核电用锆合金在最新一代核电站中应用广泛，但在核电站反应堆 高温，强辐射条件下，还是会出现辐照损伤现象。这些损伤对核电站 使用效率，寿命，成本都有显著影响。减弱锆合金的辐照损伤，提高 核电用锆合金使用寿命显得尤为重要。 本文基于透射电镜技术研究锆合金辐照损伤，观察纯锆样品在 100KeV 氢离子辐照条件下的辐照损伤表征，主要观察核电用锆合金 在高温辐照条件下，产生的位错环，通过研究这些位错环的形成原因 和形成取向，找到解决辐照损伤问题的突破口。进而探究辐照损伤的 机理与取向并提出可能的解决措施。 最终我们观测到： 1. 在样品由于晶体取向差异，位错环存在分布不均匀的现象； 2. 由于布拉格衍射条件差异，不同照片存在明场为主或者暗场为 主的现象； 3. 在已有形变带条件下，形变带中的位错环密度较形变带外显著 减少； 研究的最后，我们以形变带内外位错环密度差异为突破口，对产 生差异的原理做出了合理假设，并设计了实验来验证假设，希望进一 步的研究能为核电用锆合金辐照损伤的解决做出贡献。

Zirconium alloys are widely used in the latest generation of nuclear power plants, but radiation damage still occurs in high temperature and strong radiation conditions. These damages have a significant impact on the efficiency, life and cost of nuclear power plants. It is very important to solve or reduce the irradiation damage of zirconium alloy and improve the service life of zirconium alloy for nuclear power. In this paper, the radiation damage of zirconium alloy was studied by transmission electron microscopy (TEM), and the radiation damage characterization of pure zirconium sample under 100 Kev hydrogen ion irradiation was observed, through studying the formation cause and orientation of these dislocation rings, we find a breakthrough to solve the problem of irradiation damage. Then the mechanism and orientation of radiation damage are discussed and the possible solutions are put forward. Finally, we observe: 1. Due to the difference of crystal orientation, the distribution of dislocation loops is not uniform. 2. Due to the difference of Bragg diffraction conditions, there are mainly bright or dark fields in different photographs. 3. The density of dislocation loops in the deformation zone is significantly lower than that outside the deformation zone under the condition of the existing deformation zone. A reasonable hypothesis is made and an experiment is designed to verify the hypothesis. It is hoped that further research can contribute to the solution of irradiation damage of zirconium alloys for nuclear power.